ML19331B577

Submits Info Re Item 2d,engineered Safety Features,In Response to NRC .Qa Program Used During Design & Const Phase Ensured That Actuation Signals Equipment Met Requirements of Listed Criteria

ML19331B577
Person / Time
Site:	Beaver Valley
Issue date:	08/07/1980
From:	Dunn C DUQUESNE LIGHT CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 8008120457
Download: ML19331B577 (3)

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'Af stri 4ss-coco 435 Samm Avenue IE7'""

August 7, 1980 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:

Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Engineered Safety Features, Letter Dated April 4, 1980 Gentlemen:

In our response to your letter of April 4, 1980, we indicated that we would have the information necessary to respond to Item 2d available by August 1, 1980.

The following actuation signals were identified as Engineered Safety Feature (ESF) signals in response to your letter.

1.

Safety Injection Signal 2.

Containment Isolation - Phase A 3.

Containment Isolation - Phase B Feedwater Isolation 5.

Steamline Isolation Automatic Transfer to Recirculation 6.

These signals are safety related and, as such, are designed and qualified l

to the following criteria, codes and standards.

1.

General Design Criteria for Nuclear Power Plant Construction Permits, Federal Register, July 11, 1967.

2.

" Safety Guides for Water Cooled Nuclear Power Plants," Division of Reactor Standards, Atomic Energy Commission, October 27, 1971.

l 3.

IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations, IEEE Std. 279-1971.

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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Ehgineered Safety Peatures, Letter Dated April.4,.1980 Page 2 4.

-IEEE Standard Criteria for Class IE Electric Systems for Nuclear Power Generating Station, IEEE Std. 308-1971.

5.

IEEE Trial-Use Standard: General Guide for Qualifying Class I Electric Equipment for Nuclear Power Generating Station, IEEE Std. 323-1971.

6.

IEEE Trial-Use for Type Tests of Continuous-Duty Class I Motors Installed Inside the Containment of Nuclear Power Generating Stations, IEEE Std. 334-1971.

7.

IEEE Trial-Use Criteria for the Periodic Testing of Nuclear Power Generating Station Protection Systems, IEEE Std. 338-1971.

8.

The Institute of Electrical and Electronic Engineers, Inc., IEEE Trial-Use Guide for Seismic Qualification of Class I Electric Equipment for Nuclear Power Generating Stations, IEEE Std. 334-1971.

i 9.

IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations, IEEE Std. 279-1971.

4 In addition to the environmental design bases listed in IEEE Standard 279-1971, the following additional environmental requirements were applicable in the design of the ESF actuation signals.

1.-

During the initial phase of either a loss of coolant or steam line break accident, the engineered safety features actuation system i

will provide the required signals. Therefore, engineered safety features actuation system components are designed and arranged so that radioactive, mechanical and thermal environments accompanying l

any emergency situation in which the components are required to i

function do not interfere with that function.

2.

Prescurizer pressure and level sensors are required to operate during the first half hour following an accident or until the pressure and water level are reduced beyond the span of the instruments, whichever happens first.

3.

The containment sump level instrumentation will function for at least 3 houars following an accident.

4.

The air and motor operated containment isolation valves (Phase A and e containment isolation) will function on initiation from a safety injection signal (for Phase A) or a high-high containment pressure signal'(for Phase B).

L The quality assurance program used during the design and construction phase of Unit No.1 ensured that the ESF actuation signals equipment met the

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requirements of the above mentioned criteria.

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-w Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Engineered Safety Features, Letter Dated April 4, 1980 Page 3 If you have any questions, please contact my office.

Very truly yours,

c. N. L, C. N. Dunn Vice President, Operations cc:

Mr. D. A. Beckman, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, Pennsylvania 15077 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.

20555 I

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